CN102842346B - System for processing serious accidents caused by helium pressurization in nuclear power plant - Google Patents
System for processing serious accidents caused by helium pressurization in nuclear power plant Download PDFInfo
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- CN102842346B CN102842346B CN201210309046.2A CN201210309046A CN102842346B CN 102842346 B CN102842346 B CN 102842346B CN 201210309046 A CN201210309046 A CN 201210309046A CN 102842346 B CN102842346 B CN 102842346B
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a system for processing serious accidents caused by helium pressurization in a nuclear power plant, belonging to the field of nuclear power plant safety and the field of environment protection technologies. The system comprises two parts: a helium charging pressurization transport system and a containment wall cooling system, wherein the helium charging pressurization transport system comprises a helium supply source, a pressurization device and a heating device; the helium supply source is connected with the pressurization device by a helium output pipe; the pressurization device is connected with the heating device by a two-gas pipeline; the two-gas pipeline penetrates through a containment; the helium supply source and the pressurization device are arranged outside the containment; the heating device is arranged inside the containment; a blow pipe is arranged on the heating device; and the containment wall cooling system comprises a spray water tank, a spray drive structure, an upper spray shower nozzle and a lower spray shower nozzle. The system provided by the invention has an active and non-active dual system advantage, meets a single failure criterion, and is high in deposition efficiency of fine particulate matters.
Description
Technical field
The invention belongs to nuclear plant safety field and environmental protection technical field, particularly relate to a kind of helium pressurization in nuclear power plant major accident disposal system.
Background technology
Fukushima, Japan generation human history continued in 2011 the third time nuclear plant severe accident of USSR (Union of Soviet Socialist Republics) Chernobyl, U.S.'s Three Mile Island.The radioactive grain thing that accident produces flies away with the wind, along with air motion is transferred, brings immeasurable harm to earth environment and public health.Under the major accident of nuclear power station, a large amount of radioactive grains may be produced, effectively remove the life security that these radioactive grains are directly connected to surrounding enviroment and people.Along with the development of science and technology, existing nuclear power station technology is also more and more advanced.But, be no matter running now two generation reactor or the three generations's reactor designed, under generation major accident, all will produce radioactivity fine grained.Even the forth generation supercritical water reactor of advanced person, also also exists specific question: the graphite dust that forth generation modular pebble bed high temperature reactor produces may affect the safety of reactor and normally run; In Generation IV sodium-cooled fast reactor, the safety of the migration of sodium particle also entail dangers to security of system and around people under accident conditions.So, when nuclear power generation major accident, remove for prevention and to delay major accident be all very important to fine grain.
The fine grained that nuclear power station produces mainly PM
10, PM
2.5deng fine particle, because its quality is little, specific surface area large, fabulous to the followability of air-flow, be not easy deposition.Conventional dust collection method is all lower to these fine grain removal efficiencies, cannot meet Nuclear Safety regulation and environmental requirement.Main employing French sand drift formula filtrator, Sweden's pebble type filtrator and German venturi pipe filter in the design of current nuclear power station, mainly for be the larger fragment of reactor that produces of accident or coarse particle, unspecial in the Fine Particles under major accident.Add in nuclear power station in two generations and two generations and also remove fine grained by spray, but the major function of spray system is cooling, the effect removing particle is poor.Spray system is eliminated at three generations AP1000 presurized water reactor, adopt steel containment vessel that water tank is set during major accident and carry out decrease temperature and pressure, the design of water tank also plays the effect removing particle simultaneously, but this is not the elementary object of waterbox design, and the particulate removal weak effect of water tank.Removing for fine particle under nuclear plant severe accident, is also in the Primary Study stage at present.Therefore, in order to ensure the safety of nuclear power, the method for efficient removal fine particle must be found.
Summary of the invention
The object of the invention is to propose a kind of helium pressurization in nuclear power plant major accident disposal system for existing nuclear power technology deficiency.Helium is that inert gas can not react in containment, and helium has larger thermal conductivity, is beneficial to heat transfer, formation temperature gradient fields.In the environment in certain pressure field and temperature field, utilize fine particle thermophoretic effect and turbulence effect, can remove the fine grained that nuclear power station produces.
Helium pressurization in nuclear power plant major accident disposal system provided by the invention, comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply, pressue device and heating apparatus, described helium source of supply is connected with pressue device through helium output channel, described pressue device is connected with described heating apparatus through lose-lose feed channel, described lose-lose feed channel is through containment, described helium source of supply and described pressue device are arranged on outside containment, described heating apparatus is arranged in containment, and described heating apparatus is provided with blow line;
Described containment wall cooling system comprises: spray water tank, spray drive structure, upper spray nozzle and lower spray nozzle.
Described helium output channel is provided with valve.
On described lose-lose feed channel first gas pipe line, containment is inside and outside all arranges electronic inhaling valve; On second gas pipe line, containment is inside and outside all arranges non-active inhaling valve.
The electronic inhaling valve of the inside and outside setting of containment in lose-lose feed channel; The non-active inhaling valve of the inside and outside setting of containment is that multi-ensuring binary channels is normally run.Inside and outside containment, all set up valve, meet the redundancy principles of equipment.System cloud gray model meets nuclear power single failure principle.
Described blow line is at least one.
Described blow line is arranged and electronicly spurts valve or non-ly actively spurt valve.
Described upper spray nozzle is all connected with described spray water tank through spray drive structure with described lower spray nozzle.
Described upper spray nozzle and lower spray nozzle quantity all can be 200-600.
Described spray water tank is ring-type.
Described containment wall cooling system is located at the top of containment.
Described helium pressurization major accident disposal system of filling can take modular mounting means, both can be arranged on existing reactor when overhaul, and also can design ingredient as advanced reactor.
Beneficial effect of the present invention is: helium pressurization in nuclear power plant major accident disposal system has active and non-active dual system feature, meets single failure criteria, and the deposition efficiency of fine particle is high.
This system can install all types of nuclear power station of each generation.Especially to PM
10, PM
2.5remove important using value Deng fine particle, effectively can reduce the discharge capacity of fine particle, reach the object of protection public health and environment.This device has safety, efficient, reliable, and it is convenient to implement, and controls simple, can the feature such as modularization assembling.
When major accident appears in nuclear power station, this device fills with pressurized helium in containment; Meanwhile, to containment outer wall spray, to reduce containment wall temperature.This kind of infant industry dust arrester, using accident high-temperature gas mixture as thermal source, the outer water-cooled of containment is low-temperature receiver, forms the mixed gas temperature field that there is thermograde in containment.Utilize thermophoretic effect and turbulence effect, effectively remove the radioactivity fine grained that major accident produces.Also impel containment decrease temperature and pressure, to alleviate the harm of nuclear power major accident simultaneously.This major accident disposal system can adopt modular mode, is installed on inside and outside nuclear power plant containment shell.This System Implementation is convenient, control is simple, can ensure that nuclear plant safety high efficient and reliable is run.The helium pressurization in nuclear power plant major accident disposal system that the present invention proposes, can be applied to all types of nuclear reactor of each generation.This system effectively can remove fine particle, has important value to guarantee nuclear power station surrounding environment safety and public health.
Accompanying drawing explanation
Fig. 1 is helium pressurization in nuclear power plant major accident disposal system schematic diagram;
Number in the figure:
1-helium source of supply; 2-valve; 3-helium conveyance conduit; 4-pressue device; The outer electronic inhaling valve of containment on 5-first gas pipe line; Electronic inhaling valve in containment on 6-first gas pipe line; The outer non-active inhaling valve of containment on 7-second gas pipe line; Non-active inhaling valve in containment on 8-second gas pipe line; 9-first gas pipe line; 10-second gas pipe line; 11-heating apparatus; 12-is electronic spurts valve; 13-is non-actively spurts valve; 14-first blow line; 15-second blow line; 16-containment; 17-first time spray nozzle; 18-second time spray nozzle; 19-spray drive structure; 20-spray water tank; Spray nozzle on 21-first; Spray nozzle on 22-second.
Embodiment
The following examples and accompanying drawing can make those skilled in the art more fully understand the present invention, but do not limit the present invention in any way.
Embodiment 1
Helium pressurization in nuclear power plant major accident disposal system, comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply 1, pressue device 4 and heating apparatus 11, described helium source of supply 1 is connected with pressue device 4 through helium output channel 3, described pressue device 4 is connected with described heating apparatus 11 through lose-lose feed channel, described lose-lose feed channel is through containment 16, described helium source of supply 1 and described pressue device 4 are arranged on outside containment 16, described heating apparatus 11 is arranged in containment 16, and described heating apparatus 11 is provided with blow line;
Described containment wall cooling system comprises: spray water tank 20, spray drive structure 19, upper spray nozzle and lower spray nozzle.
Described helium output channel 3 is provided with valve 2.
On described lose-lose feed channel first gas pipe line 9, containment is inside and outside all arranges electronic inhaling valve; On second gas pipe line 10, containment is inside and outside all arranges non-active inhaling valve.
Described blow line is two, the first blow line 14 is arranged electronicly spurt valve 12, the second blow line 15 is arranged non-ly actively spurt valve 13.
Described upper spray nozzle is all connected with described spray water tank 20 through spray drive structure 19 with described lower spray nozzle.
Described spray water tank is ring-type.
Described containment wall cooling system is located at the top of containment.
The structure of helium pressurization in nuclear power plant major accident disposal system Fine Particles device as shown in Figure 1.Helium supplies helium by helium source of supply 1.During nuclear power major accident, on helium output channel 3, valve 2 is opened, and helium enters pressue device 4 thus, pressurizes; On first gas pipe line, on the outer electronic inhaling valve 5 of containment and the first gas pipe line, in containment, electronic inhaling valve 6 opens the first gas pipe line 9, or on the outer non-active inhaling valve 7 of the second containment on gas pipe line and the second gas pipe line in containment non-active inhaling valve 8 automatically open the second gas pipe line 10, helium is delivered to heating apparatus 11 by pressue device 4 by the first gas pipe line 9 or the second gas pipe line 10, injects in containment; Heating apparatus 11 pairs of high-pressure heliums are heated, heating apparatus 11 with accident high-temperature gas mixture for thermal source; Now, the electronic valve 12 that spurts opens the first blow line 14, or the non-active valve 13 that spurts opens the second blow line 15 automatically, helium is discharged in containment 16 from heating apparatus 11 by the first blow line 14 or the second blow line 15, by input helium enter in containment with other gas and vapor permeation in containment.Meanwhile, utilize spray drive structure 19 to the cooling of containment outer wall outside containment, the water source of spraying component is from ring-type spray water tank 20.Spraying component sprays water-cooled cooling by upper spray nozzle and lower spray nozzle to containment top cover and tube wall.According to different reactor heap-type, set up 200-600 spray nozzle up and down respectively, to increase the effect of spray water-cooled.Only to list on first time spray nozzle, 17, second time spray nozzle 18, first spray nozzle 22 on spray nozzle 21, second in the drawings.In containment, form the temperature gradient field under certain pressure like this, fine grained does turbulent flow and thermophoretic motion wherein, and high effective deposition in containment, thus avoids radioactive grain to leak.
Involved pressue device 4, exactly from helium source of supply 1, the helium input containment 16 with certain pressure.
Involved heating apparatus 11 is to helium raised temperature, and in cooling containment while temperature, gas temperature in intensification helium to containment 6, forms uniform temperature gradient with wall.
Electronic inhaling valve 6 in containment on outer electronic inhaling valve 5, first gas pipe line of containment on involved first gas pipe line, electronic non-active inhaling valve 8 in containment, the non-active valve 13 that spurts of spurting on outer non-active inhaling valve 7, second gas pipe line of containment on valve 12, second gas pipe line are by electronic and non-active first gas pipe line 9 or the second gas pipe line 10, first blow line 14 or the second blow line 15 two kinds of its operation functions of different path implement.Meanwhile, ensure that containment can be closed, to avoid piling interior hypertonia after passing into a certain amount of helium.Meet nuclear safety single failure principle.
Involved lower spray nozzle, spray drive structure 19, ring-type spray water tank 20, upper spray nozzle are lowered the temperature to containment outer wall, to realize the formation of temperature gradient field in containment.
The above; be only the present invention's preferably embodiment, but protection scope of the present invention is not limited thereto, is anyly familiar with those skilled in the art in the technical scope that the present invention discloses; the change that can expect easily or replacement, all should be encompassed within protection scope of the present invention.Therefore, protection scope of the present invention should be as the criterion with the protection domain of claim.
Claims (9)
1. a helium pressurization in nuclear power plant major accident disposal system, is characterized in that: this helium pressurization in nuclear power plant major accident disposal system comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply (1), pressue device (4) and heating apparatus (11), described helium source of supply (1) is connected with pressue device (4) through helium output channel (3), described pressue device (4) is connected with described heating apparatus (11) through lose-lose feed channel, described lose-lose feed channel is through containment (16), described helium source of supply (1) and described pressue device (4) are arranged on containment (16) outward, described heating apparatus (11) is arranged in containment (16), (11) are provided with blow line to described heating apparatus,
Described containment wall cooling system comprises: spray water tank (20), spray drive structure (19), upper spray nozzle and lower spray nozzle;
Described helium pressurization in nuclear power plant major accident disposal system takes modular mounting means.
2. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described helium output channel (3) is provided with valve (2).
3. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: on described lose-lose feed channel first gas pipe line, containment is inside and outside all arranges electronic inhaling valve; On second gas pipe line, containment is inside and outside all arranges non-active inhaling valve.
4. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described blow line is at least one.
5. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described blow line is arranged and electronicly spurts valve (12) or non-ly actively spurt valve (13).
6. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described upper spray nozzle is all connected with described spray water tank (20) through spray drive structure (19) with described lower spray nozzle.
7. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described upper spray nozzle and lower spray nozzle quantity are 200-600.
8. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described spray water tank is ring-type.
9. helium pressurization in nuclear power plant major accident disposal system according to claim 1, is characterized in that: described containment wall cooling system is located at the top of containment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210309046.2A CN102842346B (en) | 2012-08-27 | 2012-08-27 | System for processing serious accidents caused by helium pressurization in nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210309046.2A CN102842346B (en) | 2012-08-27 | 2012-08-27 | System for processing serious accidents caused by helium pressurization in nuclear power plant |
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| CN102842346A CN102842346A (en) | 2012-12-26 |
| CN102842346B true CN102842346B (en) | 2015-02-25 |
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1076301A (en) * | 1992-03-05 | 1993-09-15 | 苏舍热技术有限公司 | Eliminate the device of contained suspension in the interior air of nuclear reactor safety housing |
| GB2319191A (en) * | 1996-11-15 | 1998-05-20 | Boris Gorbunov | A particulate matter concentrator |
| CN101807444A (en) * | 2010-03-18 | 2010-08-18 | 华北电力大学 | Fine particle removing device of nuclear power plant |
| CN202771811U (en) * | 2012-08-27 | 2013-03-06 | 华北电力大学 | Serious accident processing system capable of charging helium and pressurizing for nuclear power station |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2770330B1 (en) * | 1997-10-24 | 2000-01-14 | Cogema | METHOD AND DEVICE FOR CONTAINMENT BY THERMAL LAMINATION |
-
2012
- 2012-08-27 CN CN201210309046.2A patent/CN102842346B/en not_active Expired - Fee Related
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1076301A (en) * | 1992-03-05 | 1993-09-15 | 苏舍热技术有限公司 | Eliminate the device of contained suspension in the interior air of nuclear reactor safety housing |
| GB2319191A (en) * | 1996-11-15 | 1998-05-20 | Boris Gorbunov | A particulate matter concentrator |
| CN101807444A (en) * | 2010-03-18 | 2010-08-18 | 华北电力大学 | Fine particle removing device of nuclear power plant |
| CN202771811U (en) * | 2012-08-27 | 2013-03-06 | 华北电力大学 | Serious accident processing system capable of charging helium and pressurizing for nuclear power station |
Non-Patent Citations (2)
| Title |
|---|
| 压水堆严重事故下气溶胶热泳沉积规律;杨林民等;《原子能科学技术》;20080131;第42卷(第1期);第63-66页 * |
| 温度梯度场内可吸入颗粒物运动特性及热泳沉积;刘若雷等;《化工学报》;20090731;第60卷(第7期);第1623-1628页 * |
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